Abstract

The use of advanced uranium-based and thorium-based fuel bundles in a 700-MW(electric)–class pressure tube heavy water reactor (PT-HWR) has the potential for improved performance characteristics with higher burnup, higher fissile fuel utilization, and lower coolant void reactivity while also extracting the energy potential in thorium. In this study, thermal-hydraulic subchannel analyses were performed for a single, high-power (6.5 MW), 12-bundle fuel channel at typical reactor operating conditions for 14 different PT-HWR lattice/core concepts using various types of advanced uranium-based and thorium-based fuels in 37-element and 35-element fuel bundle design concepts. Fuel bundle radial power distributions for fresh fuel at zero burnup were used in the thermal-hydraulic calculations, as a bounding case, along with axial power distributions that are representative of those that may be found in a high-power fuel channel in a PT-HWR core at near-equilibrium refueling conditions. The fuel bundle radial power distributions and fuel channel axial power distributions were determined from previous lattice physics and core physics studies. Based on the subchannel thermal-hydraulic analyses, the LC-05b/CC-04 BUNDLE-37-mod concept and the LC-12b/CC-08 BUNDLE-35 concept are recommended as the best candidates for further full-core system thermal-hydraulic transient analyses, based on critical heat flux and void fraction performance factors. BUNDLE-37 concept LC-01/CC-00 is also recommended as the reference case for future analysis.

摘要

在 700 兆瓦（电）级压力管重水反应堆 (PT-HWR) 中使用先进的铀基和钍基燃料束具有改善性能特性的潜力，具有更高的燃耗、更高的裂变燃料利用率和降低冷却剂空隙反应性，同时提取钍的能量潜力。在这项研究中，对使用各种类型的先进铀的 14 种不同 PT-HWR 晶格/堆芯概念在典型反应堆运行条件下的单个高功率 (6.5 MW) 12 束燃料通道进行了热工水力子通道分析。 37 元素和 35 元素燃料束设计概念中的基和钍基燃料。在热工水力计算中使用零燃耗新鲜燃料的燃料束径向功率分布作为边界情况，以及代表在接近平衡加油条件下 PT-HWR 堆芯中的高功率燃料通道中可能发现的那些轴向功率分布。燃料束径向功率分布和燃料通道轴向功率分布是根据先前的晶格物理和堆芯物理研究确定的。基于子通道热工水力分析，LC-05b/CC-04 BUNDLE-37-mod 概念和 LC-12b/CC-08 BUNDLE-35 概念被推荐为进一步全核系统热-基于临界热通量和空隙率性能因素的水力瞬态分析。BUNDLE-37 概念 LC-01/CC-00 也被推荐作为未来分析的参考案例。燃料束径向功率分布和燃料通道轴向功率分布是根据先前的晶格物理和堆芯物理研究确定的。基于子通道热工水力分析，LC-05b/CC-04 BUNDLE-37-mod 概念和 LC-12b/CC-08 BUNDLE-35 概念被推荐为进一步全核系统热-基于临界热通量和空隙率性能因素的水力瞬态分析。BUNDLE-37 概念 LC-01/CC-00 也被推荐作为未来分析的参考案例。燃料束径向功率分布和燃料通道轴向功率分布是根据先前的晶格物理和堆芯物理研究确定的。基于子通道热工水力分析，LC-05b/CC-04 BUNDLE-37-mod 概念和 LC-12b/CC-08 BUNDLE-35 概念被推荐为进一步全核系统热-基于临界热通量和空隙率性能因素的水力瞬态分析。BUNDLE-37 概念 LC-01/CC-00 也被推荐作为未来分析的参考案例。LC-05b/CC-04 BUNDLE-37-mod 概念和 LC-12b/CC-08 BUNDLE-35 概念被推荐为基于临界热通量的进一步全核系统热工水力瞬态分析的最佳候选者和空隙率性能因素。BUNDLE-37 概念 LC-01/CC-00 也被推荐作为未来分析的参考案例。LC-05b/CC-04 BUNDLE-37-mod 概念和 LC-12b/CC-08 BUNDLE-35 概念被推荐为基于临界热通量的进一步全核系统热工水力瞬态分析的最佳候选者和空隙率性能因素。BUNDLE-37 概念 LC-01/CC-00 也被推荐作为未来分析的参考案例。